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Development of tokamak experiment technology -A study on the nuclear fusion reactor-

Technical Report:

Abstract

Overall test operation of KT-1 tokamak has been done with the modified power supplies and constructed plasma position feedback control system. The achieved plasma parameters of KT-1 are Ip (plasma current) > 15 kA (9ms) and Td (plasma current sustaining time) > 12 ms (7.5 kA) until now. Instrumentations for the carbonization/boronization are also equipped and applied to the first boronization of invessel components of KT-1 tokamak. As a preliminary treatment of the 1st wall of tokamak vacuum torus, RG discharge cleaning has been done. Plasma qualities have been improved by discharge cleaning. In addition, helicon plasma device is designed succeeding exploitation of the first wall conditioning program which are all for the development of conditioning technology of 1st wall facing the plasma. As a part of the development program on the plasma monitoring technologies, conceptual design study on the FIR interferometer- polarimeter is accomplished. Parallel to these experimental activities, an effort has been made in designing the operating scenario of poloidal field system of KT-2 tokamak. (Author).
Authors:
Lee, Kwang Won; Hwang, Chul Kew; In, Sang Ryul; Kim, Sung Kyu; Oh, Byung Hoon; Jeong, Seung Ho; Hong, Bong Guen; Yoon, Jae Sung; Yoon, Byung Joo; Song, Woo Sup; [1]  Park, Byung Ho; [2]  Park, Byung Ki; Lyu, Ji Myung [3] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
  2. Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)
  3. Seoul National Univ., Seoul (Korea, Republic of)
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1363/93
Reference Number:
SCA: 700412; PA: AIX-26:013716; EDB-95:033383; SN: 95001325578
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; TOKAMAK DEVICES; PERFORMANCE TESTING; CONTROL EQUIPMENT; PLASMA PRODUCTION; POLARIMETERS; POLOIDAL FIELD DIVERTORS; THERMONUCLEAR REACTORS; 700412; MAGNETIC CONFINEMENT DEVICES
OSTI ID:
10112910
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95614255; TRN: KR9400194013716
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
211 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Lee, Kwang Won, Hwang, Chul Kew, In, Sang Ryul, Kim, Sung Kyu, Oh, Byung Hoon, Jeong, Seung Ho, Hong, Bong Guen, Yoon, Jae Sung, Yoon, Byung Joo, Song, Woo Sup, Park, Byung Ho, Park, Byung Ki, and Lyu, Ji Myung. Development of tokamak experiment technology -A study on the nuclear fusion reactor-. Korea, Republic of: N. p., 1994. Web.
Lee, Kwang Won, Hwang, Chul Kew, In, Sang Ryul, Kim, Sung Kyu, Oh, Byung Hoon, Jeong, Seung Ho, Hong, Bong Guen, Yoon, Jae Sung, Yoon, Byung Joo, Song, Woo Sup, Park, Byung Ho, Park, Byung Ki, & Lyu, Ji Myung. Development of tokamak experiment technology -A study on the nuclear fusion reactor-. Korea, Republic of.
Lee, Kwang Won, Hwang, Chul Kew, In, Sang Ryul, Kim, Sung Kyu, Oh, Byung Hoon, Jeong, Seung Ho, Hong, Bong Guen, Yoon, Jae Sung, Yoon, Byung Joo, Song, Woo Sup, Park, Byung Ho, Park, Byung Ki, and Lyu, Ji Myung. 1994. "Development of tokamak experiment technology -A study on the nuclear fusion reactor-." Korea, Republic of.
@misc{etde_10112910,
title = {Development of tokamak experiment technology -A study on the nuclear fusion reactor-}
author = {Lee, Kwang Won, Hwang, Chul Kew, In, Sang Ryul, Kim, Sung Kyu, Oh, Byung Hoon, Jeong, Seung Ho, Hong, Bong Guen, Yoon, Jae Sung, Yoon, Byung Joo, Song, Woo Sup, Park, Byung Ho, Park, Byung Ki, and Lyu, Ji Myung}
abstractNote = {Overall test operation of KT-1 tokamak has been done with the modified power supplies and constructed plasma position feedback control system. The achieved plasma parameters of KT-1 are Ip (plasma current) > 15 kA (9ms) and Td (plasma current sustaining time) > 12 ms (7.5 kA) until now. Instrumentations for the carbonization/boronization are also equipped and applied to the first boronization of invessel components of KT-1 tokamak. As a preliminary treatment of the 1st wall of tokamak vacuum torus, RG discharge cleaning has been done. Plasma qualities have been improved by discharge cleaning. In addition, helicon plasma device is designed succeeding exploitation of the first wall conditioning program which are all for the development of conditioning technology of 1st wall facing the plasma. As a part of the development program on the plasma monitoring technologies, conceptual design study on the FIR interferometer- polarimeter is accomplished. Parallel to these experimental activities, an effort has been made in designing the operating scenario of poloidal field system of KT-2 tokamak. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}